American Nuclear Society

Total Page:16

File Type:pdf, Size:1020Kb

American Nuclear Society AMERICAN NUCLEAR SOCIETY . 555 North Kensington Avenue Tel: 708 / 352-6611 La Grange Park, Illinois E-Mail: [email protected] 60526-5592 USA http: //www.ans.org Fax: 708 / 352-6464 AUTHOR PROOF INSTRUCTIONS Your paper is scheduled for publication in a forthcoming issue of Nuclear Technology. You are receiving your author proofs electronically. You will not receive anything in the regular mail. Please follow these procedures: 1. Download your author proof, print it out, and review it. 2. Proofread your paper very carefully. This will be your final reading before publication. This material has been copyedited and typeset from the disk/electronic file that you provided with your manuscript or from the hard copy that you provided, and it has been transmitted to you through the Internet. This process produces excellent results, but please check the following especially carefully: translation of Greek letters, accented letters, special characters, superscripts and subscripts, and mathematical symbols; typesetting of mathematics; and formatting of tables. Also, note that your manuscript has been copyedited according to ANS technical journal style; please check that technical meanings have been unaffected by the copyediting. Please limit your corrections to those that are absolutely necessary because changes at this stage of processing are both time-consuming and expensive. 3. Please note that the typesetter has used low-resolution electronically scanned versions of your figures as FPOs (for position only). These will be replaced with high-resolution versions at the printing stage. 4. Necessary corrections should be sent as follows: (a) a list of corrections sent by electronic mail and/or (b) your manuscript with your corrections marked on it sent by fax (your fax should include a list of your corrections). If you have been sent a list of queries, we would greatly appreciate your reply to these queries either by electronic mail or by fax. 5. Please return your corrections within a week of receipt of your author proofs. Note that delay in transmitting your corrections may delay publication of your paper or may require publication without your corrections. 6. Return proofs using the following name and electronic mail address or fax number: Brian Fitzgerald E-mail: [email protected] Fax: 708-352-6464 Thank you for your prompt attention to these proofs. If you have any questions, please feel free to contact me. Brian Fitzgerald Staff Editor Leaders in the development, dissemination and application of nuclear science and technology to benefit humanity . NT 6-08022NQ 10102016009 2:15 pm NT-6 08022NQ QUERIES ||||||1||||||> Please provide three keywords. ||||||2||||||> Added “magnetically channeled spherical IEC array.” Is this the correct definition of “MCSA” as it is used here? ||||||3||||||> Changed “of a deuterium” to “of a deuterium beam.” Is this correct? ||||||4||||||> Is “10130m3” correct? Should there be a unit of measure after “1013”? ||||||5||||||> Changed “this equation” to “Eq. ~20!.” Is this correct? ||||||6||||||> Is “10190m3” correct? Should there be a unit of measure after “1019”? ||||||7||||||> In the original manuscript’s References list, Refs. 3, 11, and 23 were identical. We deleted Refs. 11 and 23 and renumbered subsequent references. Is this okay? ||||||8||||||> In the original manuscript’s References list, Refs. 4, 6, and 22 were identical. We deleted Refs. 6 and 22 and renumbered subsequent references. Is this okay? ||||||9||||||> In the original manuscript’s References list, Refs. 8 ~now Ref. 7 because of the deletion of original Ref. 6! and 9 were identical. We deleted Ref. 9 and renumbered subsequent references. Is this okay? ||||||10||||||> There is no callout in the text for Ref. 19 ~which was Ref. 24 in the original manuscript!. Please place a callout for Ref. 19 in the text of the paper. ||||||11||||||> Please specify if “Kammash ~1995!” corresponds to Ref. 11, Ref. 12, or both. ||||||12||||||> There is no corresponding reference in the References list for “Cheung ~2004!.” Please provide reference information for this study. ||||||13||||||> Do “Burton ~2001!” and “Burton ~2004!” correspond to Ref. 7? If not, please provide reference infor- mation for these study. NT 6-08022N 10602017009 11:54 am NT-6 08022N MAGNETICALLY CHANNELED IEC MISCELLANEOUS TRAP ARRAY FUSION DEVICE FOR TECHNICAL NOTE KEYWORDS: xxxxxxxx, xxxxx, INTERPLANETARY MISSIONS xxxxxx <||||||1|||||| GEORGE H. MILEY,* HIROMU MOMOTA, and LINCHUN WU University of Illinois at Urbana-Champaign, Urbana, Illinois 61801 Received January 24, 2008 Accepted for Publication July 1, 2008 A radical new inertial electrostatic confinement (IEC) fu- Thus, the MCTA concept has the potential to accomplish the de- sion concept, the magnetically channeled IEC trap array (MCTA), manding requirements of future deep-space propulsion and power is studied as a candidate power unit for interplanetary space by providing a high power-density propulsion system. This prom- travel. IEC fusion concepts are widely recognized to be attrac- ise was amply demonstrated in an earlier, reasonably detailed tive for space power because they are simple and lightweight. design study by University of Illinois researchers that used a However, existing experimental IEC concepts, while very suc- magnetically channeled spherical IEC array (MCSA) to accom- <||||||2|||||| cessful for low-level power neutron sources, do not project to plish a fast manned mission to Jupiter. high-power space applications because of poor confinement- In the present paper, we discuss the basic MCTA concept time scaling and grid heating/losses. The MCTA concept ad- and examine stability issues that must be resolved to access the dresses both issues: eliminating the need for a central grid by feasibility of this concept. Some important supporting data injecting energetic ions into this unique hybrid configuration carry over from prior IEC experiments, but a full MCTA con- and providing improved confinement by connecting a number figuration has yet to be studied experimentally. If proven feasi- of traps. Because of the linearly connected geometry and com- ble, the MCTA development path would involve experiments at patibility with an efficient traveling wave direct-energy con- progressively higher powers aimed at the ultimate demonstra- verter, aneutronic fuels, such as D-3He, can be implemented. tion of a full-scale, several-hundred-MW propulsion unit. I. INTRODUCTION propulsion study at the University of Illinois can be traced back to the 1980s, when field reversed mirror was proposed.3,4 Based I.A. Prior Work on the study of IEC ~Ref. 5!, space propulsion using an IEC device was studied.4,6 It is then followed by the concept of Study of space propulsion using fusion power began in the “Fusion Ship I” and “Fusion Ship II” ~Ref. 7! with traveling late 1950s and was further developed after the 1980s, espe- wave direct energy converters ~TWDECs!, as shown in Fig. 1. cially exploring improved fusion confinement concepts. Sev- Fusion Ship II is 300 m long, and the initial mass at mis- eral additional power approaches have been brought out since sion start is 500 t. The crew and avionics0computer are located then. These include field reversed configurations ~FRCs!, spher- in the central compartment at the front end of the vehicle. The omaks, dense plasma focus, inertial electrostatic confinement twin 175-m-long assemblies are comprised of five D-3He spher- ~IEC!, magnetic dipoles, and so on. A historical review of ical IEC reactors connected to a TWDEC. They can generate research in fusion propulsion1 is briefly listed in Table I, show- 1394 MW of 14.7-MeV proton flux and 469 MW of thermal ing specific power, thrust power, and specific impulse. The components, which are converted to 1197 MW~electric! of RF items are listed in the order of the different concept groups electric power, 242 MW of which recirculates to run the reac- discussed above. Details of these conceptual designs can be tors with 750 MW~electric! used to drive the ion thrusters and found in the references included.1–18 the remainder being heat loss. The ion thrusters run on argon propellant at a specific impulse of 35 000 s and an efficiency of I.B. IEC-Based Space Propulsion 90%. The thrust is 4369 N, which produces an initial acceler- ation of 0.0087 m0s2. A typical trip time for an out-and-back Specifically, recent studies of IEC-powered space propul- mission to Jupiter is 210 days out and 152 days to return. The sion at the University of Illinois are summarized in Table II, very large size and open design of Fusion Ship II minimizes along with a magnetic fusion concept2 as a comparison. Fusion the need for thermal radiators, which are not shown in Fig. 1. The IEC itself has a skeletal structure allowing radiation to be *E-mail: [email protected] emitted directly to space. The TWDEC uses molybdenum grids NUCLEAR TECHNOLOGY VOL. 166 JUNE 2009 1 NT 6-08022N 20602017009 11:54 am Page: 2 Miley et al. MAGNETICALLY CHANNELED IEC TRAP ARRAY FUSION DEVICE FOR INTERPLANETARY MISSIONS TABLE I Fusion Propulsion Conceptual Studies Specific Power Thrust Power Specific Impulse, Isp First Author Fusion System ~kW0kg! ~MW! ~s! Kulcinski9 ~1987! Tandem mirror ;2 1 000 Santarius10 ~1988! Tandem mirror 2.2 1 000 Carpenter13 ~1992! Tandem mirror 4.3 Kammash ~1995! Gas dynamic trap 7.5 55 000 1.1 ϫ 105 <||||||11|||||| Kammash ~1995! Gas dynamic trap 21 ~D-T! <||||||11|||||| Teller14 ~1991! Dipole 0.5 to 1 1 250 104 to 3 ϫ 105 Bussard15 ~1990! Tokamak 3.7 3 925 5 ϫ 103 to 7 ϫ 103 Borowski16 ~1987! Spheromak 11.5 5 500 5 ϫ 104 Borowski16 ~1987! Spherical torus 5.8 6 000 2 ϫ 104 Williams17 ~1998! Spherical torus 5.4 6 145 4 ϫ 104 Williams2 ~2001! Spherical torus 8.62 4 830 35 435 to 47 205 Nakashima18 ~1994! FRC 1 103 to 106 Cheung ~2004! Colliding beam FRC 3 100 1.4 ϫ 106 <||||||12|||||| Thio4 ~1999! Magnetized target fusion 400 25 000 7.7 ϫ 104 Borowski16 ~1987! Integral Fast Reactor 110 53 000 2.7 ϫ 105 Burton ~2001! IEC 0.17 500 1.6 ϫ 104 <||||||13|||||| Burton ~2004! IEC 1.5 750 3.5 ϫ 104 <||||||13|||||| Santarius10 ~1998! D-Ta 0.6 600 Santarius10 ~1998! D-3Hea 5.3 600 Santarius10 ~1998! D-3Hea 10.1 600 aGeneric one.
Recommended publications
  • A 14 Mev Neutron Source Based on Gas Dynamic Trap Concept. Status and Perspectives E.P
    30th EPS Conference on Contr. Fusion and Plasma Phys., St. Petersburg, 7-11 July 2003 ECA Vol. 27A, P-2.189 A 14 MeV Neutron Source Based on Gas Dynamic Trap Concept. Status and Perspectives E.P. Kruglyakov, A.A. Ivanov, Yu.A. Tsidulko Budker Institute of Nuclear Physics, 630090, Novosibirsk, Russia Besides the main physical problems of controlled fusion such as physics of alpha particles, ignition, etc, there exists a problem of a limited lifetime of structural materials under intensive bombardment by 14 MeV neutrons, degradations of their electrical and mechanical properties, accumulation of impurities, etc. At present, the development of the world fusion program is concentrated on the ITER project. However, even in the case of success of this project it cannot serve a function of high power neutron source for candidate material tests for future fusion power plant because of low fluence. Indeed, irradiation of one of the existing candidates on the role of a material for the first wall (ferritic-martensitic steel) with 14 MeV neutron flux of order of 2 MW/m2 during 10 years will lead to the level of radiation damages of 200 dpa. The ITER will provide only about 2 dpa per year. Thus, the fusion reactor cannot be built without performing extensive program dedicated to qualify the materials to be used in the reactor core under high level irradiation by 14 MeV and secondary neutrons. In other words, the final goal of the controlled fusion program can not be achieved without urgent design and construction of a dedicated high power 14 MeV neutron source (NS).
    [Show full text]
  • Axisymmetric Tandem Mirror D-T Neutron Source
    Axisymmetric Tandem Mirror D-T Neutron Source W. Horton∗ and J. Pratt University of Texas at Austin, Institute for Fusion Studies A.W. Molvik Lawrence Berkeley National Laboratory R.M. Kulsrud, N.J. Fisch Princeton Plasma Physics Laboratory I. OVERVIEW We propose to harness an axisymmetric tandem mirror machine to create an intense neutron source[1] [2]. Our machine would be initially based on the successful GAMMA-10 tandem mirror experiment in Tsukuba, Japan and the Gas Dynamic Trap (GDT) mirror experiment in Novosibirsk, Russia. In addition it would be suitable for testing of several other axisymmetric stabilization methods: kinetic stabilizers [3] [4], sloshing ions, and wall stabilization, which would enable higher-Q operation than with GDT-type stabilization. The GAMMA-10 has achieved record breaking confinement results that extrapolate to the production of fusion power in a range of fusion Q from 0.1 to 5 in the near future [5]. In this work the authors outline a linear system that could produce large neutron fluxes in a spectrum nearly identical to that of the ITER device currently being built[6]. A hydrogen prototype of a D-T mirror neutron source would allow experiments on stabilization in axisymmetric cells and expanders that would lead to an optimized fusion Q design. Optimizations are needed for fusion-fission hybrid designs versus pure fusion designs. II. ADVANTAGES OF TANDEM MIRRORS The linear axisymmetric system has major conceptual advantages over all toroidal systems. We list a few of these advantages here: (1) Simplicity of engineering with no interlinked magnetic-field coils and no volt-second transformer considerations.
    [Show full text]
  • Preparation and Submission of a Manuscript for the Proceedings
    1 OV/P-07 Fusion Prospects of Axisymmetric Magnetic Mirror Systems A.D.Beklemishev1,2, A.V.Burdakov1,3, A.A.Ivanov1,2, E.P.Kruglyakov 1 1Budker Institute of Nuclear Physics of SB RAS, Novosibirsk, Russia 2Novosibirsk State University, Novosibirsk, Russia 3Novosibirsk State Technical University, Novosibirsk, Russia E-mail: [email protected] Abstract. Studies of magnetic mirrors for fusion started 60 years ago. The evolution of mirrors was driven by needs to stabilize curvature-driven instabilities and reduce axial losses. It turned them into highly sophisticated and huge tandem mirrors with axial ambipolar confinement, thermal barriers and quadrupole magnetic stabilizers [1,2]. Too late it was recognized that quadrupole fields cause resonant radial losses, and that placing stabilizers behind barriers reduces their effectiveness. Tandem mirrors lost competition to toroidal devices in 1987 and are almost extinct. A side branch of open traps went for simplicity, high-β and good fast-ion confinement inherent in axially symmetric mirrors [3]. These traits allow lower cost of construction and servicing, lower engineering and materials demands, promise a path to advanced-fuels fusion. Axially symmetric mirrors are of particular interest as neutron sources or fusion-fission hybrids. They might still have an edge as pure fusion reactors. Axially symmetric mirrors at the Budker Institute of Nuclear Physics in Novosibirsk currently represent the frontline of mirror research. We discuss recent experimental results from the multiple-mirror trap, GOL-3 [4], and the gas- dynamic trap, GDT [5]. The next step in this line of research is the GDMT program that will combine the GDT- style fast-ion-dominated central mirror with multiple-mirror end plugs [6].
    [Show full text]
  • Emerging Concepts Reactor Subgroup Summary J
    LA-UR-99-5178 Emerging Concepts Reactor Subgroup Summary J. Hammer and R. Siemon Emerging Concepts offer unique reactor features, which may lead to a qualitative improvement in cost and maintainability, with associated increased attractiveness to the customer. Table 3 shows some of these unique features grouped by concept: Concept Motivation RFP Low external field; no disruptions Spheromak, FRC Simple geometry; small size; open axial divertor MTF, Flow Pinch Low development cost; compatible with liquid walls Levitated Dipole, Centrifugally confined High β, classical confinement; no current drive Mirrors Low physics risk; linear geometry Electrostatic, IEC, POPS Small unit size; low-cost development; high mass power density; alternate applications Fast Igniter High gain; low recirculating power Table 3: Reactor features of Emerging Concepts. Again, many examples of reactor advantages associated with Emerging Concepts could be given. As one such, there appears at first examination to be a greater accessibility for incorporating liquid walls into many such reactors. This follows from the linear, open geometry of several of the concepts, including FRC, MTF, Flow Pinch, and Mirrors. Organization The reactor subgroup, jointly with the Physics subgroup, heard presentations arranged before the conference on the 11 concepts listed below. These covered a wide range in physical parameter space with radically different reactor embodiments. The reversed field pinch and spheromak talks were held jointly with the Magnetic Confinement sessions. For each concept, a presenter introduced the concept and reviewed progress to date and important physics and reactor issues. The presenter was followed by a reviewer who brought additional insights. Concept Presenter Reviewer RFP S.
    [Show full text]
  • The Fairy Tale of Nuclear Fusion L
    The Fairy Tale of Nuclear Fusion L. J. Reinders The Fairy Tale of Nuclear Fusion 123 L. J. Reinders Panningen, The Netherlands ISBN 978-3-030-64343-0 ISBN 978-3-030-64344-7 (eBook) https://doi.org/10.1007/978-3-030-64344-7 © The Editor(s) (if applicable) and The Author(s), under exclusive license to Springer Nature Switzerland AG 2021 This work is subject to copyright. All rights are solely and exclusively licensed by the Publisher, whether the whole or part of the material is concerned, specifically the rights of translation, reprinting, reuse of illustrations, recitation, broadcasting, reproduction on microfilms or in any other physical way, and transmission or information storage and retrieval, electronic adaptation, computer software, or by similar or dissimilar methodology now known or hereafter developed. The use of general descriptive names, registered names, trademarks, service marks, etc. in this publication does not imply, even in the absence of a specific statement, that such names are exempt from the relevant protective laws and regulations and therefore free for general use. The publisher, the authors and the editors are safe to assume that the advice and information in this book are believed to be true and accurate at the date of publication. Neither the publisher nor the authors or the editors give a warranty, expressed or implied, with respect to the material contained herein or for any errors or omissions that may have been made. The publisher remains neutral with regard to jurisdictional claims in published maps and institutional affiliations. This Springer imprint is published by the registered company Springer Nature Switzerland AG The registered company address is: Gewerbestrasse 11, 6330 Cham, Switzerland When you are studying any matter or considering any philosophy, ask yourself only what are the facts and what is the truth that the facts bear out.
    [Show full text]
  • Axially Symmetric Magnetic Mirror Traps
    AXIALLY SYMMETRIC MAGNETIC MIRROR TRAPS. RECENT PROGRESS IN PLASMA CONFINEMENT AND HEATING E.P. Kruglyakov, A.V. Burdakov, A.A. Ivanov Budker Institute of Nuclear Physics, Novosibirsk, Russia New results of studies of plasma heating and confinement in the axisymmetric mirror traps are presented. It is shown that due to excitation of the instability at the bounce frequency (bounce instability) the effects of multi-mirror confinement can observed even at the densities by two-three-orders of magnitude lower than those predicted by the Budker, Mirnov and Ryutov theory (GOL-3 facility). This effect makes the multi-mirror reactor more realistic. A small size mirror cell was incorporated with the gas dynamic trap (GDT). Due to the transverse injection of two neutral beams (ENB=20 keV) ion hot plasma was obtained in the compact mirror cell. As a result of that the plasma flux to the end wall decreased by 5 times. Besides, the threshold of the Alfven ion cyclotron instability (AIC) was determined in the same experiment with accumulation of fast ions in the compact cell. It follows from this experiment that in the GDT based neutron source the AIC instability will not excite in spite of anisotropic plasma. PACS: 52.55.Jd INTRODUCTION The main idea of the GDT NS is as follows. A flux of Among the systems for plasma confinement there are fast atoms of D and T is injected into a warm plasma under some traps with open-ended magnetic field lines, which an angle to the axis and captured there. As a result, a strongly differ from the systems with closed magnetic population of sloshing ions of high energy is created.
    [Show full text]
  • Development of GDT-Based Fusion Neutron Source on a Path to Fusion Energy
    Development of GDT-based Fusion Neutron Source On a path to fusion energy C.B. FOREST, J. Anderson, J. Egedal, V. Mirnov, A. Molvik, E. Peterson, J.S. Sarff, T. Simonen, O. Schmitz, J. Wallace and R. Waleffe, R. Harvey, Y. Petrov, D. Whyte, R. Mumgaard SHINE: Fusion-Fission Hybrid for Mo99 production using T beam into D gas target Tritium ion beam high pressure deuterium Uranium blanket Outline 1.There have been recent game changing results in Gas Dynamic Trap mirror research 2.Fast ions confined in a steady-state GDT could be a very efficient neutron source for many applications (isotope production, radiography, neutron capture therapy) ➡ offers a cost-effective short cut to fusion materials and sub-component testing 3.The mirror, like tokamaks, benefits from new high field magnet technology and other technological developments (eg. high frequency steady-state gyrotrons, lithium walls, negative neutral beams) 4.Near term experiments and theory effort could: ➡ determine if GDT neutron source is feasible ➡ be test bed for high field magnets and lithium walls 5. The fast development path of linear systems, may only require one or two miracles beyond the GDT to improve confinement for fusion energy: there are still good ideas 3 1. GDT Axisymmetric MHD Stability Beta = 2 mu0 P/B2=60% Limiter or End Wall Bias + Curvature (MSE UW) 2. GDT D-D Neutron Production Illustrates Lack of Micro-Instabilities Axial Profile Radial Profile also demonstrated tandem mirror like plugging (nfast>2 ne(z=0) at turning points) 3. GDT Electron Temperature Reaches 1
    [Show full text]
  • Fusion Yield Registration in the Gas Dynamic Trap
    Fusion Yield Registration in the Gas Dynamic Trap E.I. Pinzhenin1, a) and V.V. Maximov1, 2, b) 1BINP SB RAS, Novosibirsk Russia 2NSU, Novosibirsk Russia. a)Corresponding author: [email protected] b)[email protected] Abstract. The diagnostics for a fusion reaction of the product registration at the Gas dynamic trap facility during the deuterium neutral beam injection is described in this review. Both 3.02 MeV protons and 2.45 MeV neutrons registrations are used in GDT experiment. The advantages of the registration of these two products are discussed in the paper Also the fusion reaction intensity and the neutron flux parameters are presented in the article. In addition, the new multichannel diagnostics with the improved parameters are discussed here. GAS DYNAMIC TRAP FACILITY FIGURE 1. Gas dynamic trap device. Gas dynamic trap facility (GDT) is an axisymmetric magnetic mirror trap for the fusion plasma confinement Figure 1, [1]. There are two components of the GDT plasma: the first one is a warm plasma component with the electron temperature about 250 eV and density of up to 6 1019 m-3 (warm plasma is confined in a collisional regime that means that the effective ion mean free path of scattering into the loss cone is less than a mirror-to-mirror distance). The second component produced by oblique neutral beam injection is strongly anisotropic fast ions. This component has the mean energy of 10 keV and density up to 1019 m-3. These fast ions are confined in the collisionless regime. There are fusion reactions in GDT during the deuterium neutral beam heating: D + D -> 3He (0.82 MeV) + n (2.45 MeV) 50% D + D -> T (1.01 MeV) + p (3.02 MeV) 50% Both branches occur with the same probability (for the GDT conditions and for the accuracy of our experimental data).
    [Show full text]
  • Summary of Physics Aspects of Some Emerging Concepts
    Summary of Physics Aspects of Some Emerging Concepts EC Working Group, Physics Issues SubGroup, Snomass Workshop 1999 Convenors: J. Kesner and A. Hassam 9/23/99 Field Reversed Configurations (FRC's) ===================================== FRC's are attractive because of the simplicity of configuration. There is no central column and there are no toroidal fields. Once formed in the lab, they are robust - they are stable, can be compressed, and can be translated with ease. This immediately leads to the question, which remains the central question of FRC research and future direction: why are FRC's so stable? In particular, all field lines are closed and the curvature is unfavorable, hence, the flux tubes should be interchange or kink unstable according to well known MHD theory. The answer is simple: ideal MHD theory is inapplicable. MHD theory is applicable only in systems where there are many ion Larmor radii across the system scale. In addition, Alfvenic forces, the stabilizer of MHD theory, are the correct paradigm only in systems where there are many ion collisionless skin depths across the system. For the FRC's created in the lab to date, both these conditions fail. The maximum number of Larmor radii for an FRC in the lab is probably about 4 and since FRC's are by definition beta = 1 devices, the collisionless skin depth is equal to the Larmor radius. Thus, MHD notions cannot be applied and, apparently, FLR effects and Alfven -> whistler effects are stabilizing. There is also another effect - the elongation. FRC's are generally elongated objects and the usual MHD instabilities, such as interchanges and kinks, have reduced growth rates with elongation.
    [Show full text]
  • A Neutron Source Based on Gas Dynamic Trap for Fusion-Fission Hybrid Systems A.V
    40th EPS Conference on Plasma Physics P2.110 A neutron source based on gas dynamic trap for fusion-fission hybrid systems A.V. Anikeev 1,2 , P.A. Bagryansky 1,2 , S.A. Brednikhin 1,3 , S.A. Frolov 1,3 , S.I. Lezhnin 1,3 , V.V. Prikhodko 1,2 , Yu.A. Tsidulko 2 and D.V. Yurov 1,2,3 1 Novosibirsk State University, Novosibirsk 630090, Russia 2 Budker Institute of Nuclear Physics SB RAS, Novosibirsk 630090, Russia 3 Nuclear Safety Institute RAS, Novosibirsk 630090, Russia 1. Introduction To become an economic and save energy supplying technology nuclear fusion research has to solve several material problems. The most critical of them are caused by intense irradiation of high energetic neutrons. To develop appropriate materials, which can withstand the high neutron load, suitable neutron sources are necessary as irradiation facilities for testing material samples. Since the start of nuclear fusion programme various proposals for such a facility were made. For a number of years the Budker Institute of Nuclear Physics, Novosibirsk, Russia in collaboration with the domestic and foreign organizations develop the project of 14 MeV neutron source, which can be used for fusion material studies and for other application [1,2]. The projected neutron source of plasma type is based on the plasma Gas Dynamic Trap (GDT), which is a special magnetic mirror system for plasma confinement [3]. Compared to others, that of a GDT-based neutron source has essential advantages. A research activity of the Budker Institute aims at completing the database of the GDT in the range of high plasma parameters, which are relevant for the neutron source, and at demonstrating its feasibility and suitability by prototype experiments.
    [Show full text]
  • Parameter Optimization Studies for a Tandem Mirror Neutron Source
    J Fusion Energ DOI 10.1007/s10894-010-9332-9 ORIGINAL RESEARCH Parameter Optimization Studies for a Tandem Mirror Neutron Source W. Horton • X. R. Fu • A. Ivanov • A. Beklemishev Ó Springer Science+Business Media, LLC 2010 Abstract A basic plasma physics tandem mirror experi- alpha particles born in the core of the plasma with a ment is proposed to develop the potential uses of magnetic relatively large gyroradius. The recent example of the mirror confined plasmas for a neutron source. We consider intrinsically long single particle confinement time is parameter variations from the currently operating sym- given by the 300 s electron confinement time in the metric mirror plasma trap GDT in an attempt to optimize RT1 dipole experiment at the University of Tokyo [1]. the neutron source intensity while minimizing the expense 2. No toroidal curvature that is responsible for the and complications of the system. The combined radial and uniform unfavorable magnetic curvature over large axial plasma loss rates are analyzed and shown to yield an volumes of the plasma. A torus of major radius R has 2 optimal operational point that minimizes the required an effective gravity from the geff = cs/R over the auxiliary heating power. whole outer-half of the torus. This produces a magnetic type of Rayleigh–Taylor instability that Keywords Mirror confinement Á Tandem mirror Á limits the plasma pressure to low values in MHD and Neutron source Á Nuclear fusion produces long fingers of vortices in the drift wave turbulence that rapidly transport particles and energy radially across the machine’s minor radius r = a.
    [Show full text]
  • MHD Stability and Confinement of Plasmas in a Single Mirror Cell
    Digital Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology 155 MHD Stability and Confinement of Plasmas in a Single Mirror Cell NATALIA SAVENKO ACTA UNIVERSITATIS UPSALIENSIS ISSN 1651-6214 UPPSALA ISBN 91-554-6497-1 2006 urn:nbn:se:uu:diva-6637 !" "##$ !#%!& ' ' ' ( ) * + ( , - .( "##$( /0 , 1 ' ' , / 1( ( !&&( 2 !## ( ( 3,4. 5!6&&76$7586!( ) ' ' ' ( 3' '' * ' * ( ) ' * 4 ' ' ' * /0 ' ' ' ' 9 ' ( , ' ( 1 ' :;!# ' <( 1 * ' ( ' ' = '>( ) 1 ' * ' ' '( ) 1 ' ? @ ' ( ) * @ ' ' 9 ( 1 ' ' ' ' ' ( 1 * '' ' 9 A#(" ( ' ( ' ' ' @ ( /0 ' ! " # " # $ %" & ' ()*" " #+,(-.- " B . , - "##$ 3,,. !$&!6$"!7 3,4. 5!6&&76$7586! % %%% 6$$C8 D %EE (-(E F G % %%% 6$$C8H To my parents Nina & Alex iv List of Papers This thesis is based on the following papers, which are referred to in the text by their Roman numerals. I O. Ågren, and N. Savenko, ‘Magnetic mirror minimum B field with optimal ellipticity’, Physics of Plasmas, 11, 5041, (2004). II O.
    [Show full text]